Summary : EXC, EXS and PPC Y. Kamada, QST

26th IAEA FEC

Papers: EXC 101, EXS 57, PPC 26 from 40 devices

MEDUSA (Costa Rica ): R~0.14m, a~0.1cm, GLAST-III (Pakistan): R=0.2m, a=0.1 m

........ JET (EU): R~3m, a~1.2m

W7-X, Welcome to EX sessions !

2

Start New Operation

NSTX-U

Ip~1MA H-modes,

H98 ≥ 1, βN ~4 ≥ n=1 no-wall limit

with weak/no core MHD

SST-1

Upgraded with Plasma

Facing Components.

KTX

University of Science and

Technology of China

RFP

R=1.4m, a=0.4m

Ip=0.5MA (=>1MA)

Bt max=0.35T (=>0.7T)

Welcome to EX !

3

Contents

1. Edge Pedestal System

2. Core Transport

3. Core MHD Stability

4. Operation & Control

* Disruption Mitigation is treated

in the next talk by Dr. D. Hill

4

Core Pedestal P

res

su

re

(T, n

)

Shafranov Shift Fast particles

Plasma Shape (k, d, A)

B field (3D): RMP ~

plasma response

impurity

D Heat & Particle

to Divertor

Turbulence

EHO,

WCM, QCM

Diffusion

Pinch

Width

ELM

Stochasticity

EDA H-mode

I-mode

QH-mode

grad-p: ELM = Peeling-Ballooning modes (PBMs)

width: small-scale turbulence( KBM...)

Grassy ELM mitigation

H-mode Pedestal Structure and Dynamics

minor radius

5

Flow

Heig

ht

small/no ELM

regimes

Pressure Gradient ~ Peeling Ballooning Mode

JET and JT-60U:

confirmed in a wide space

of (k,d). Low k high d

gives lower grad-p, but

wider pedestal width, then

grassy ELM & good

confinement.

(EX/3-4, Urano )

JT-60U and JET: MINERVA-DI: Rotation can

destabilize PBMs due to

minimizing the 𝜔∗𝑖 effect =>

better fit to exp. data.

(TH8-1, Aiba)

Multi-machine: JOREK

simulations at low

resistivity/viscosity

reproduce experiment

(TH8-2, Pamela)

JET

TCV, MAST and

JET :The pedestal

height has been

significantly

increased by early

increase of bp-core.

(EX3-6, Chapman)

COMPASS:The

experimental data

are in agreement

with the EPED

model. (EXP6-35,

Komm)

6

TCV

COMPASS

MHD simulations reproduce

experiment very well.

Shafranov shift stabilizes the pedestal gradient,

ELM crash new key findings

KSTAR: Three-stage evolution of ELM

was identified using a 2D imaging: (1)

quasi-steady filamentary mode with long

life time n=4-15, (2) abrupt structural

transformation into filaments with

irregular poloidal spacing near the onset

of crash, (3) and multiple filament bursts

during the crash. (EX10-3, Yun)

Pegasus: J-edge across single

ELMs shows the nonlinear

generation and expulsion of

current-carrying filaments.

(EXP4-51, Bongard)

7

Pedestal evolution during the ELM cycle

8

ASDEX-U: 70ms resolution Ti (r)

measurement: At ELM, heat flux is

first increased at the separatrix, then

Ti(r) becomes flatter. ci comes back

soon to its pre-ELM neoclassical

level . (EXP6-30, Viezzer)

JET: Pedestal evolution during the ELM cycle:

not always consistent with EPED (EX3-3, Maggi)

Low D2 Gas:

low-bN: Gradient increases and width constant:

not consistent with KBM constraint

?

Is J-edge expelled

by an ELM crash?

ASDEX-U: D fueling shifts density profile

outward , and T profile anchored at separatrix

=> causes a significant degradation of the

pedestal top pressure. (EX3-5, Dunne)

Pedestal Width: key = ne(r) relative to Te,i (r)

9

JET: Pedestal stability improves with

reduced radial shift. JET-ILW tends to

have larger relative shift than JET-C.

(EXP6-13, Giroud)

Te

ne

pe

pp

ed

ne,sep(1019m-3)

L-H Transition Threshold Power

DIII-D: Dual Mode Nature of

Edge Turbulence May

Explain Isotope and Density

Scaling of L-H Power

Threshold (EX5-1, Yan)

JET: Isotope Effect: Non-

linear mass dependence on

L-H power threshold (EX5-

2,Hillesheim)

PD, Nunes)

KSTAR: PLH increases with

δB for any cases with n=1,

n=2 or mixed-n. (EXP4-4)

Pegasus

NSTX

MAST

10

Th

res

ho

ld P

ow

er

Pegasus: Ultralow-A

At low A(~1.2), PLH >> ITPA

scaling by one order of

magnitude.(OV5-4, Fonck)

L-H transition: Behavior of turbulence

JET: Radial wavelength of

Stationary Zonal Flows scales

with the radial correlation

length of turbulence,

~ several times smaller

than the width of the edge

radial electric field well.

(EX5-2, Hillesheim)

NSTX: The energy exchange between flows and

turbulence was analyzed using GPI .The edge fluctuation

do not vary just prior to the H-transition.

=> Turbulence depletion is probably not the mechanism of

the L-H transition in NSTX. (EX5-3, Diallo)

DIII-D: The main-ion poloidal

flow acceleration is quantitatively

consistent with Reynolds-stress-

driven shear flow amplification

( EXP3-11, Schmitz)

11

ASDEX-U: L-I Transition: Negligible contributions

of ZFs. (EXP6-29, Putterich)

ELM-free regimes : extended remarkably

DIII-D: Discovered Stationary

Quiescent H-mode with Zero Net

NBI Torque in double-null shaped

plasmas, characterized by

increased pedestal height & width:

sustained for 12tE with excellent

confinement (H98y2 ~ 1.5, 𝛽N ~ 2).

(EX3-2, Chen) decreased

edge ExB

shear enables

destabilization

of broadband

turbulence

QH-mode I-mode Alcator C-mod :

High energy confinement with Temperature pedestal,

L-mode Density pedestal, Small impurity, Stationary

and ELM-free. Extended to full field 8T and current

1.7MA. Confirms weak L-I threshold dep. on B, and

wide power range at high B. (EX3-1, Hubbard)

12

7.8 T ,1.35 MA

Te0 =7.3keV

<p>=1.4 atm

H98=1

KSTAR: Broadband

turbulence induced by RMP

damps the ELM amplitude

(EXP4-15, Lee)

HL-2A: EM turbulence was

excited by locally-

accumulated impurities.

Double critical gradients of

impurity density were

observed and reproduced

by theoretical simulation. (OV4-4, Duan)

HL-2A: Synchronization of GAMs and

magnetic fluctuations was observed in the

edge plasmas. (EXP7-27, Yan)

13

Pedestal fluctuations : variety of interplay

EAST: A new stationary small/no

ELM H-mode was found at low

𝜈𝑒∗ < 0.5, H98 ≳ 1.1, exhibiting a

low-n electro-Magnetic Coherent

Mode. It appears at the low

frequency boundary of TAE gap.

(+ ELM pacing)(EX10-2, Xu)

Remaining Issue:

How is the Pedestal Width determined ?

Pre

ss

ure

(T, n

)

?

?

When pedestal grad-p is below Peeling-Ballooning limit,

how does the pedestal width evolve and saturate ?

During the ELM cycle?

Controllable? 14

Success of RMP ELM Suppression = Phase and Shape

DIII-D: ELM control requires

the applied field to couple to

an edge stable MHD mode,

directly observed on high field

side. The response is

inversely proportional to n*.

(EX1-2, Paz-Soldan) (AUG : EXP6-25, Willensdorfer

MAST: peeling, OV5-3, Kirk )

ASDEX + DIII-D: ELM

Suppression was obtained

for the first time in AUG at

low n* with a plasma shape

matched to DIII-D (d~0.3)

showing the importance of stable edge kink response.

(PD, Nazikian)

KSTAR: Optimal phasing for

n=1 RMP is consistent with

an ideal plasma response

modeling.(EX1-3, In)

EAST: n=1 RMP, Plasma response

behaves a nonlinear transition from

mitigation to suppression of the

ELMs (EXP7-4, Sun)

15

Long Pulse ELM Suppression by RMP: Big Progress

DIII-D: Fully Noninductive plasmas

with high 𝛽 (≤ 2.8%) and high

confinement (H≤ 1.4) sustained for

≤ 2 current relaxation with ECCD

and NBCD, and integrated with

ELM suppression by n=3 RMP; the

strong resonant interaction allows

ELM suppression over a wide

range of q95 (EX4-1, Petty)

KSTAR: n=1 RMP ELM suppression was sustained for

more than ~90 tE (H89=1.5), and also confirmed to be

compatible with rotating RMP, wide q95 (4.75 – 5.25)

(EX1-3, In), (PD, Jeon)

16

DIII-D KSTAR EAST

EAST: n=1 RMP ELM suppression in long-pulse (> 20s)

was realized with small effect on plasma performance

(H98>1) (P7-4, Sun)

Te/Ti ~ 1 ( <= electron heating (a, high energy NB, IC, ECH), high ne)

Small rotation due to small external torque ( => intrinsic torque )

Small central fueling ( high energy NB) => density profile ?

Accumulation of heavy impurity (metal wall) ?

Confinement performance with metal divertor can be recovered?

Core Plasma Transport issues for ITER & DEMO

Isotope Effects on Confinement?

17

Electron Transport

Thermal Transport at high Te/Ti

18

DIII-D / JT-60U

ci {

Hig

h T

e/Ti

}

ci {

Low

Te/

Ti}

magnetic shear

DIII-D and JT-60U: Positive Shear (PS) shows

reduction in Ti when ECH is added. Negative

Central Shear (NCS) minimizes confinement

degradation even with increasing Te/Ti~1. DIII-

D shows smaller rise in low-k turbulent

fluctuations in NCS than PS. (EX8-1, Yoshida)

Σñ

{H

igh

Te/

Ti}

Σñ

{Lo

w T

e/Ti

}

PS

NCS

Fluctuation

DIII-D

JET: High Te/Ti plasmas: Electron

transport evaluated with linear

gyro-kinetic simulations GENE:

most consistent with

( ITG/TEM) + ETG.

=> Multi-scale non-linear gyro-

kinetic simulation underway.

(EXP6-14, Mantica)

R/LTe

qegB

Te/Ti~1

Electron thermal Transport

NSTX: Electrostatic low-k Gyrokinetic

Simulation (GTS) explains ion thermal

transport , but is not able to explain electron

transport. => high-k ETG / EM is important for

electron transport. Nonlinear GYRO simulation

explains grad-n stabilization of ETG, but not

enough => EM? (EXP4-35, Ren)

MST: Drift wave turbulence

(TEM) emerges in RFP

plasmas when global

tearing instability is

reduced by PPCD.

(EXP5-17, Brower)

19

MAST: Fluctuation

measured at the top of

pedestal is consistent

with Electron transport

evaluated with linear

gyro-kinetic simulations

GENE: consistent with

ETG. (OV5-3, Kirk)

electron

W-7X: Te profile shape follows the ECRH

Power deposition

-> no indication of profile stiffness

(EX4-5, Hirsch)

Density Profile => low n* ITER ?

DIII-D: The density scale length R/Ln

is well-correlated with the frequency

of the dominant unstable mode, with

the peaking when the turbulence

switches from ITG to TEM.

(EXP3-9, Mordijck)

DIII-D: Change in peaking is

reproduced by changes in core fueling only . (EXP3-9, Mordijck)

JET: Density peaks with

decreasing * => experimentally

determined particle transport

coefficients. =>suggest that NBI

fueling is the main contributor to

the observed density peaking.

(EXP6-12, Tala)

FTU: The density profile

evolution in high density regime

has been well reproduced using

a particle pinch term with

dependence on temperature

gradients (U= DT /Te ∂Te/∂r)

(EXP8-24, Tudisco)

20

ISTTOK:Edge electrode biasing improves particle

confinement by reducing radial transport via ExB shear

layer formation. (EXP7-36, Malaquias )

R/L

ne

n*

1) The maximum H98 increases

at lower n*.

2) H98 increases with βN,

however for metal wall H98

significantly reduced (~0.8-0.9)

at βN≤1.8, H98~1 is obtained

only for βN~2 or higher.

(EX6-42, Sips)

Confinement towards ITER: high bN is the key

21

JET-ILW: stationary (5s)

ITER Baseline Operation

at high-d (~0.4) achieved

at 2MA/2.2T, q95=3.2.

New high-d configuration

optimized for pumping

H=1-1.1, bN=1.8-2.1 but

n/nGW~ 0.5 (EX/P6-11, De la Luna)

AUG, C-Mod, DIII-D, JET and JT-60U:

Stationary H-mode discharges at q95=2.7-3.3:

Metal

CFC

bN

bN

H98y2

H98y2

Avoidance of Heavy Impurity Accumulation ~ good

JET: W/ ICRF minority

Central ICRH is beneficial on tungsten

transport in the ITERbaseline scenario

JET

Alcator C-mod: W / ICRF minority (EXP3-3, Reinke )

HL-2A:Al / ECH

m/n=1/1

(EXP7-21, Cui)

T-10: W / ECH

After ECRH start a fast

decay of core radiation

occurs. (EXP8-36,

Nurgaliev)

KSTAR: Ar / ECH ( EXP4-18, Hong)

22

ASDEX-U: Central ECH and ICRH to

NB heated H-mode shows the impact

of Qe/Qi on the impurity turbulent

diffusion as predicted by Nonlinear

gyrokinetic simulations with GKW

(THP2-6, Angioni)

ASDEX-U

ITER Prediction: No

strong W accumulation

expected in ITER Q = 10

plasmas due to low NBI

fueling. W accumulation in

H-L transitions can take

place, optimization of

heating and fueling ramp-

down required. (PPC2-1,

Loarte)

(EXP6-16, Goniche )

Impurity Transport in the helical system:

rotation shear & turbulence drive

LHD: Carbon density profile peaks

with decreasing Mach number ~

rotation gradient (EXP8-4, Nakamura).

23

TJ-II: Dual HIBP: ECRH enhances

turbulence and amplitude of Long-Range-

Correlations (LRC) for potential.

(EXP7-44, Hidargo)

Intrinsic Torque & NTV

DIII-D + JET : The

total intrinsic torque

in the plasma is

found to increase at

lower r* (=favorable

way to ITER).

(EX11-1 Grierson

EXP3-13 Degrassie)

DIII-D : Simulations

with GTS gyro-

kinetic code

reproduces

reversal of core

intrinsic rotation

(EX11-1 Grierson)

KSTAR+NSTX: Neoclassical Toroidal

Viscosity (NTV) Torque: The measured

rotation profile change due to the 3D

field (EXP4-33, Sabbagh)

24

Alcator C-mod: Direction

of core rotation changes

in the following LHRF

injection depends on the

whether q0 is below or

above unity.

(EXP3-2,Rice)

Confinement: Isotope Effects / Mass Dependence

Heliotron-J: The turbulence scale size

increases as D2 gas becomes dominant. = The

first evidence for the isotope effect on

turbulence-zonal flow system in helical

systems. (EXP8-20: Ohshima)

RFX-mod: 3D RFP Confinement is

better for D than H (OVP-2, Zuin)

25

Improved Confinement Performance: ITB

DIII-D: Large radius ITB and excellent

confinement due to Shafranov Shift

Stabilization. (EX4-2, Qian)

HL-2A: Ion ITB

was observed at

the q=1 surface.

ITG is suppressed

by the toroidal

rotation shear.

(EX8-2, Yu)

LHD: High Ti & Te > 6 keV were

simultaneously achieved by high

power ECH injected into NB heated

plasmas characterized by

simultaneous formation of electron

and ion ITBs. (PPC1-1, Takahashi).

26

Multiple Machine: Transport

hysteresis in core plasmas is

widely observed.

The core hysteresis involves two

elements:

1. Interaction at long distance

2. Direct influence of heating on

transport/fluctuations

=>‘The heating heats turbulence’

(OVP-8, Itoh)

Modulation ECH: Difference between results from the

inward pulse and the outward pulse becomes larger as

the harmonic number increases ( EXP8-15, Kobayashi)

Transport hysteresis & non-localness

KSTAR: The non local transport (NLT) can be

affected by ECH, and the intrinsic rotation direction

follows the changes of NLT. (EXP4-17, Shi) 27

harmonic number of modulation

J-TEXT: RMP increases the density limit

from less than 0.7nG to 0.85nG and

lowers the limit of the edge safety factor

from 2.15 to 2.0. (OVP-6, Zhuang)

Effects of 3D field on equilibrium & stability

LHD: Phase shifted magnetic islands

from externally imposed m/n = 1/1 RMP

was obserbed (EXP8-8, Narushima)

DIII-D & RFX-mod : Role of MHD dynamo in

the formation of 3D equilibria.

high-b tokamak :The MHD dynamo model

predicts current redistribution consistent with

DIII-D experiments

(EX1-1, Piovesan )

DIII-D (core)

28

EXTRAP T2R: The resonant MP produces

tearing mode braking and locking consistent

with the prediction. (EXP5-18, Frassinetti )

Sawtooth, high b stability

KSTAR: validated q0>1 after

sawtooth crash: tearing mode

evolve (e.g. 3/3 to 2/2, 1/1)

(EXP4-3, Park, EXP4-27, Ko)

29

RELAX: The discharge duration is limited(RWM). The

central bp~15% was achived in the Quasi-Single

Helicity (QSH) state.(EXP5-22, Masamune)

LHD: Central b of the

super dense core plasma

is limited by "core density

collapse" (CDC). A new

type of ballooning mode

destabilized from the 3D

nature is the cause of the

CDC. (EXP8-10, Ohdachi)

Disruption Prediction/Characterization

NSTX: Disruption Event Characterization and

Forecasting (DECAF) code has the potential to

track RWM stability in real-time for disruption

avoidance. (Berkery, EX/P4-34 )

ADITYA: The current quench time is inversely

proportional to q-edge. (Tanna, OV/4-3Rb)

Alcator C-mod & EAST: Developing Disruption

Warning Algorithms Using Large Databases.

(EXP3-8, Granetz)

30

LHD: High-b ~ 4% was

produced by multi-pellet

injections at low n*.

Improved particle

confinement was observed

during a high-beta discharge

produced by gas-puff.

(EX4-4, Sakakibara)

Expanded High b Regimes

KSTAR: High bN, up to 4.3

was achieved with high ratios of bN/li up to 6.3. High bN ~

3.3 was sustained for 3 s,

and was limited by a 2/1

tearing mode.

(EXP4-2, Park)

31

PEGASUS: With Local

Helicity Injection (LHI),

bt~100% was achieved, often

terminated by disruption

(n=1)

(OV5-4, Fonck)

Operation: Plasma Current Rump-up ITER & DEMO

DIII-D: There are strong

interactions between Te,

fluctuation, thermal transport,

safety factor, and low-order

rational surfaces.

(EXP3-10, McKee)

32

MAST: In Ip ramp-up, the real

current diffusion is slower

than TRANSP. But, it is well

modeled during Ip flat

top.(OV5-3, Kirk)

By optimization of both Te

and q profiles, ~20%

reduction of flux

consumption is possible.

JA-DEMO: Reduction of

CS flux consumption at Ip

ramp-up

(EX/P8-38, Wakatsuki)

=> CS size

= economy of DEMO

Improved modeling is needed for DEMO design

Control of ITER & SC tokamak operation

For ITER Plasms Control system (PCS)

• Preliminary design of the ITER PCS

focusing on the needs for 1st and early

plasmas. (EXP6-36, Snipes)

• Control analysis and design tools

developed at DIII-D have been applied in

studies supporting the ITER PCS design.

(EXP6-37, Humphreys)

Real-time Error

Field Correction:

Varies correction

field amplitude

phase to maximize

plasma rotation

33

• Generation of the disruption mitigation.

(EXP6-38, Pautasso)

KSTAR: Extending vertical stabilization

controllability (EXP4-12, Hahn)

0 2 4 6 8 10 12 140

0.1

0.2

0.3

0.4

0.5

0.6

number of shots

ato

ms/

mo

lecu

les

(Pa.

m3)

D2 removed

He pumped

Total pressure

BV+BR

BV only

TCV: EC wall conditioning for JT-60SA

(EXP8-31, Douai)

KSTAR: Trapped Particle

Configuration for EC

plasma breakdown

(EXP4-14, Lee)

Seoul National UniversityFusion and Plasma Application Laboratory

1

ECH-assisted plasma start-up using trapped particle configurationin KSTAR

Efficient ECH-assisted startup using TPC than field null

600 kW / 170 GHz 2nd harmonic, toroidal field 2.7 T

Early, low Vloop, and fast Ip initiation with ~1018 m-3 pre-ionization plasmas

Widen operation range in terms of D2 prefill, poloidal field strength, and “reduced Et”

EX/P4-14

Implementation of the TPC start-up scheme to ITER based on KSTAR results

Validation of TPC with identical ECH/ECCD condition of ITER

TPC field structure made by ITER geometry, by using PF#1 and #6

Successful start-up with ITER-level Et, less than 0.3 V/m

J. Lee, J. Kim, Y.H. An, M.G. Yoo, Y.S. Na and Y.S. Hwang (SNU, NFRI)

Advanced control

F. Felici et al. - IAEA 2016 Kyoto, Summary slide. EX/P8-33

EC

po

we

rs [

MW

]

0

0.5

1P

A

PB

βt (

%)

0.2

0.3

Estimate

Ref.

Ga

s c

md

0

2

4

time [s]

0 0.5 1 1.5 2

<n

e>

V [

m-3

]

× 10 19

0

1

2

Estimate

Ref.

TCV#54534

EC

po

we

rs [

MW

]

0

0.5

1P

A

PB

βt (

%)

0.2

0.3

Estimate

Ref.

Ga

s c

md

0

2

4

time [s]

0 0.5 1 1.5 2

<n

e>

V [

m-3

]

× 10 19

0

1

2

Estimate

Ref.

TCV#54534

Real-time model-based plasma state estimation, monitoring and control on TCV, AUG and ITER

[Real-time control]

Tokamak

Controllers

Plasma

State

Recon-

stuction

Supervision

Actuator manage-

ment

actuator control systems

actuator control systems

actuator control systems

ControllersControllers

actuators diagnostics

Plasma forecasting & off-normal

event detection

• Future tokamaks will rely on advanced algorithms in PCS

• State estimation merging multiple

diagnostics.

• Model-based plasma controllers

• Real-time actuator management

• Plasma supervision

• Model-based event prediction

• These are being developed and tested on TCV and AUG in view of their application in ITER, examples:

• Real-time state reconstruction based on real-

time RAPTOR code + RT-diagnostics

• Predictive controller of plasma beta tested on

TCV (figure right)

• Numerical optimization of plasma evolution

during ramp-up and ramp-down

TCV: Beta is

estimated by

model-based and

controlled with

two gyrotrons to

follow Ref.

34

Realtime tokamak simulation with a first-

principle-based neural network turbulent

transport model (EX/P6-45, Citrin)

TCV, ASDEX-U & ITER: Real-time model

-based plasma state estimation

(EX/P8-33, Felici)

KSTAR: Physics-Based Profile Control

(EX/P4-13, Kim)

DIII-D :demonstrated

Adaptive Real-Time

Pedestal Control with

RMP by real time

stability evaluation

(EXP3-21,Kolemen)

NSTX-U: Feedback Control Using

TRANSP for Non-inductive Scenarios

(EX/P4-43, Boyer)

DIII-D : Physics-model-based q-profile

Feedback Control (EXP3-23, Schuster)

STOR-M: Toroidal Flow was modified

through Momentum Injection by CT Injection

(EXP7-39, Xiao )

FT-2: Improved Core Confinement

Observed with LHCD (EXP7-41, Lashku)

ASDEX-U: Fully non-inductive

operation with W wall at Ip= 0.8

MA( 40% NBCD, 50 % boostrap,

10 % ECCD). ECCD is used to

tailor current profile for optimum

stability and qmin > 1.5

(PD, Stober)

Steady-state Advanced Tokamak Operation Extended

KSTAR: Fully non-inductive

current drive with fBS < 0.5,

βp > 3, βN ~ 2, H89 ~ 2.0

with NBCD & ECCD

(Ip=0.45MA) (EXP4-1, Yoon)

EAST: 60sec H-mode

Demonstration of full-CD (LHCD, ECCD, ICRRF)

with W wall, βP~1.1; q95~6.3, t/tR~15,

H98>1.1.(EX4-3, Garofalo)

35

36

New Tokamak World Record of

volume averaged pressure 2.05atm

was achieved in Alcator C-mod

Summary: EXC, EXS and PPC

37

ITER

Understanding of H-mode & ELMs, and practical control scenarios

have been progressed toward ITER.

( such as, wide applicability & steady-state ELM mitigation by

RMP, understanding of confinement with W-divertor )

'3D' has become more common language and tool.

Transport / turbulence / instabilities are reproduced well by

simulations

Width of the H-mode pedestal

Electron Transport / multiple scale transport

Disruption Prediction

Enhanced Effort towards SS tokamak operation

Encouragements towards next FEC